ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
E. A. Mogahed, ARIES Team
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 1079-1083
Fusion Power Reactors (Poster Session) | doi.org/10.13182/FST98-A11963757
Articles are hosted by Taylor and Francis Online.
Loss of coolant accident (LOCA) analysis is performed for ARIES-ST. ARIES-ST is a fusion power plant design based on the spherical tokamak concept to serve as a commercial power plant. It is assumed that the plasma is immediately quenched at the onset of the LOCA and the chamber components begin to increase in temperature due to the afterheat generated. This analysis examines the thermal behavior of the in-vessel components to determine the maximum temperature reached and addresses various schemes of afterheat removal. The thermal behavior of the reactor following a LOCA is simulated using a transient two-dimensional finite element model.
